L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes
Letter Sequence Response to RAI | |
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Initiation Administration | |
MONTHYEARML16007A4602016-01-0707 January 2016
[Table View]NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for License Amendment Request Supporting Spent Fuel Pool Criticality TS Changes Project stage: Acceptance Review ML16144A8052016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Cover Letter Response to RAI Project stage: Response to RAI ML16160A0772016-06-24024 June 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes2017-02-16016 February 2017 Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes Project stage: Response to RAI ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 Project stage: Meeting ML17093A6012017-04-0606 April 2017 March 9, 2017, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Spent Fuel Pool Criticality License Amendment Request Project stage: Meeting L-PI-17-014, Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121...2017-04-19019 April 2017 Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121... Project stage: Meeting ML17279A1242017-09-30030 September 2017 Enclosure 5 to L-PI-17-041, Westinghouse WCAP-17400-NP, Supplemental 1, Revision 2, Spent Fuel Pool Criticality Safety Analysis Supplemental Analysis Including the Storage of Ifba Bearing Fuel Project stage: Supplement ML17279A1202017-10-0404 October 2017 Response to Request for Additional Information Re License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes Project stage: Response to RAI L-PI-17-041, Enclosure 6 to L-PI-17-041, Westinghouse Affidavits2017-10-0404 October 2017 Enclosure 6 to L-PI-17-041, Westinghouse Affidavits Project stage: Other ML17279A1212017-10-0404 October 2017 Enclosure 2 to L-PI-17-041, Westinghouse-Prepared RAI Responses CE-17-3, Rev. 1, Attachment 2 and Enclosure 3, Marked-Up Technical Specification Page 4.0-7 Project stage: Other ML17313B1902017-11-13013 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF7121 and MF7122; EPID L-2015-LLA-0002) Project stage: Withholding Request Acceptance ML17334A1782017-11-30030 November 2017 Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary Project stage: Approval 2017-11-30 |
ML17047A454 | |
Person / Time | |
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Site: | Prairie Island |
Issue date: | 02/16/2017 |
From: | Northard S Northern States Power Company, Minnesota, Xcel Energy |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CAC MF7121, CAC MF7122, L-PI-16-100 | |
Download: ML17047A454 (2) | |
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Prairie Island Nuclear Generating Plant Xcel Energy 1717 Wakonade Drive East Welch, MN 55089 L-PI-16-100 February 16,2017 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Response to NRC Request for Information- License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122)
References:
- 1) Letter from Kevin Davison (NSPM) to NRC (Document Control Desk),
"License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes," dated November 17, 2015 (ADAMS Accession No. ML15327A244)
- 2) Email from Robert Kuntz (NRC) to Glenn Adams (NSPM), "Official Use Only- Proprietary Information Enclosed- Request for Information Related to the Prairie Island SFP Criticality Analysis License Amendment Request (CAC Nos. MF7121 and MF7122)", dated October 31, 2016 In a letter to the U.S. Nuclear Regulatory Commission (NRC) dated November 17, 2015 (Reference 1), the Northern States Power Company, a Minnesota corporation doing business as Xcel Energy (hereafter "NSPM"), requested an amendment to the Technical Specifications (TS) for Prairie Island Nuclear Generating Plant (PINGP).
Specifically, NSPM proposed to revise Technical Specification (TS) 3.7.16, "Spent Fuel Storage Pool Boron Concentration," and TS 4.3.1, "Fuel Storage Criticality," to allow spent fuel pool (SFP) storage of nuclear fuel containing a boron-based neutron absorber in the form of zirconium diboride (ZrB2) Integral Fuel Burnable Absorber (IFBA).
The IFBA-Gd spent fuel pool criticality analysis submitted by Reference 1 followed published NRC guidance (DSS-ISG-201 0-01 ), utilized NRC approved methods, and was consistent with the Prairie Island Licensing Basis. To complete their review, the NRC staff provided a second request for additional information (RAI)- Reference 2.
The NRC requested that two reactivity effects be treated as biases in the criticality analysis as opposed to uncertainties. This treatment deviates from the established guidance (DSS-ISG-201 0-01) and the established Prairie Island licensing basis.
Document Control Desk Page 2 Further, there is no established NRC guidance to describe an acceptable analytical methodology for calculating these reactivity effects and combining them as biases.
Because the response to the RAI requires the application of first-of-a-kind factors, the fuel vendor (Westinghouse) relied upon very conservative assumptions and criticality models in developing the draft RAI responses. NSPM's current understanding of the model results is that they will unnecessarily constrain spent fuel loading in the pool and will result in unnecessary fuel movements without a commensurate increase in safety.
NSPM is working with the NRC's Licensing PM to schedule a public meeting for further discussion of the RAis and clarity regarding the NRC's new treatment of these two reactivity effects. Concurrently, NSPM is working with its fuel vendor to refine and utilize more realistic assumptions in the criticality model. NSPM's RAI responses are dependent upon the above two actions and NSPM will refine its schedule for responding to the RAis after the public meeting is conducted.
If there are any questions or if additional information is needed, please contact Glenn Adams at 612-330-6777.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on February 16, 2017
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Scott Northard Vice President- Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota cc: Regional Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC State of Minnesota